proposed ts 3/4.4.3, 'rcs leakage,leakage detection sys.' · re'actor coolant system...

APoLICABILITY

SURVEILLANCE RE UIRBIENTS Continued

ASIDE Boiler and Pressure VesselCode and applicable Addendaterminology for inserviceinspection and testin activities

Required frequenciesfor performing inserviceinspection and testingactivities

'AeklyMonthly

quarter ly or every 3 monthsSemiannually or every 6 months

Every 9 monthsYearly or annually

At 1 eastAt leastAt leastAt leastAt leastAt least

once peronce peronce peronce peronce peronce-per

7 "ays3. "ays92 claysI84 days275 aays366 aays

c. The provisions of Specification 4.0.2 are aoplicable .o the aooverequired freq'uencies for performing inservice inspection and testingactivities.

d. Performance of the above inservice inspection and testing ac ivitiesshall be in addition to other specified Surveillance Requirements.

e. Nothing in the ASHE Boiler and Pressure. Vessel Code shall beconstrued to supersede the requirements of any Technicalifi n.

The Inservice Inspection Program forpiping identiQed in NRCGeneric Letter 88-01 shall be performed in accordance with the NRCStaQ'position on Schedule, Methods and Personnel, and sampleexpansions included in the Generic Letter.

SUS/UEHANNA - UNIT 1 3/4 0-3 Amendment No. 78

9Sae|waa9e 93O4|6FOR Anacin Oaooos87P 'DR

RE'ACTOR COOLANT SYSTEM

3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE

LEAKAGE DETECTION SYSTEMS

LIMITING CONDITION FOR OPERATION

3.4.3. 1 At least the following reactor coolant system leakage detectionsystems shall be OPERABLE:

a. Two drywell floor drain sump level channels, and

b. One primary containment atmosphere gaseous radioactivity monitoringsystem channel and o'e containment atmosphere particulate radio-activity monitoring system channel aligned to the drywell.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION

a. With one or both channels of the drywell floor drain sump levelmonitoring system inoperable be in at least HOT SHUTDOWN within .the

ours and in COL HUTDOWN within the following 24 hours.QPERhhioU &4'nu~ ~ up ~~~4~ ~~~> b. ith bo channels of the gaseous radioactivity monitoring systemt4KDeqlu~~ p~,~'noperable or with both channels of the particulate radioactivityz<»q~ onitoring system inoperable, operation may continue for up to 30

ays provided grab samples of the containment .atmosphere aretained and analyzed at least once per 24 hours. If at least oneannel of the affected monitoring system cannot be returned toERABLE status and aligned to the drywell within 30 days, or the

rab samples are not obtained and analyzed as required, be in atleast HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWNwithin the following 24 hours.

SURVEILLANCE RE UIREMENTS

4. 4.3. 1 The reactor coolant system leakage detection systems shall bedemonstrated OPERABLE by:

a.

b.

Primary containment atmosphere particulate and gaseous monitoringsystems-performance of a CHANNEL CHECK at least once per 12 hours, aCHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNELCALIBRATION at least once per 18 months.

Drywell floor drain sump level monitoring system-performance of aCHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNELCALIBRATION at least once per 18 months.

SUSQUEHANNA - UNIT 1 3/4 4-6 Amendment No. 87

REACTOR COOLANT SYSTEM

OPERATIONAL LEAKAGE


3.4.3.2'a s

b.

C.

Reactor coolant system leakage shal 1 be limited to:No PRESSURE BOUNDARY LEAKAGE.

5 gpm UNIDENTIFIED LEAKAGE.

25 gpm total leakage averaged over any 24-hour period.

d. 1 gpm leakage at a reactor coolant system pressure of 1000 S 10 psigfram any reactor cooiant system pressure isolation vaive specifiedin Table 3.4.3.2-1.

Z<

llfg EEP IEAEAGE I Ef y Il.-l pLw Qe880%~~ C~>L><iJ ~.

APPLICABILI: PERATIONA ONOITIONS 1, 2 and 3.

ACTION:

ae

b.

C.

d.

I'ith

any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN'within12 hours'nd in COLO SHUTDOWN within the next 24 hours.

With any reactor coolant system leakage greater than the limits in band/or c, above, reduce the leakage rate to within the limits within4 hours or be in at least HOT SHUTDOWN within the next 12 hours andin COLO SHUTDOWN within the following 24 hours.

With any reactor coolant system pressure isolation valve leakagegreater than the above limit, isolate the high pressure portion of theaffected system from the low pressure portion within 4 hours by useof at least one closed manual or deactivated automatic valves, or bein at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN

within the following 24 hours.

With one or more of the high/low pressure interface valve leakagepressure monitors shown in Table 3.4.3.2-1 inoperable, restore theinoperable monitor(s) to OPERABLE status within 7 days or verify thepressure to be less than the alarm pressure at least once per 12 hours;restore the inoperable monitor(s) to OPERABLE status within 30 days orbe in at least HOT SHUTDOWN within the next 12 hours and in COLO

SHUTDOWN within the foll ing 24 hCc&bleow K cN;i

With any reactor coolant system U D IFIED GE ncrease greaterthan 2 gpm within any -hour period, identify the source of leakageincrease as not service sensitive Type 304 or 316 austenitic stainlesssteel within +'hours or be in at least HOT SHUTDOWN within the next12 hours and in COLO SHUTDOWN within the following 24 hours..

SUS(UEHANNA - UNIT 1 3/4 4-7 Amendment No. 36



4.4.3.2. 1 The reactor coolant system leakage shall be demonstrated to bewithin each of the above limits by:

a. Monitoring the primary containment atmospheric particulate andgaseous radioactivity at least once per 4 hours, and

b. Monitoring the drywell floor drain sump level at least once per+he s.<Z

c. Determining the total IDENTIFIED LEAKAGE at least once per 24 hours.

4.4.3.2.2 Each reactor coolant system pressure isolation valve specified inTable 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing pursuant toSpecification 4.0.5 and verifying the leakage of each valve to be within thespecified limit:

a. At least once per 18 months, and

b. Prior to returning the valve to service following maintenance, repairor replacement work on the valve which could affect its .leakage rate.

The provisions of Specification 4.0.4= are not applicable for entry intoOPERATIONAL CONOITION 3.

4.4.3.2.3 The high/low pressure inter face valve leakage pressure monitors shallbe demonstrated OPERABLE with the alarm setpoints per Table 3.4.3.2-1 byperformance of a:

a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and

b. CHANNEL CALIBRATION at least once per 18 months.

SUSQUEHANNA - UNIT 1 3/4 4-8 Amendment No. 87

3/4. 4 REACTOR COOLAlIT SYSTOLE

bASES Contfnued

~8p'f

LU pI~

UJ

'2

pbig

3/4. 4. 2 SAFETY/RELIEF VALVES

The safety valve function of the Safety/relfef valves operate to preventthe reactor coolant system froa being pressurized above the Safety Lfaft of1325 Psig in accordance ith the AQIE Code. A total of lO OPERABLE safetyrelief valves is required to i)aft reactor pressure to vfthfn AQlE III ~ llow-able values for the worst case upset transient.

Oemons<ratfon of the safety/relief valve lift sett)ngs v)11 occur onlyduring shutdown and v)11 be perforsed fn accordance fifth the provisions ofSpecification 4. 0. S.

3/4. 4.3 REACTOR COOLAHT SYSTEH LEAKAGE

3/4. 4. 3. 1 LEAKAGE OETECTION SYSTEMS

The RCS leakage detectfon systems reoufred by this specificat)on areprovided to aonftrr and detect leakage from the reactor COolant pressur»boundary.

3/4.4.3.2 OPERATIONAL LEAKAGE

The alliable leakage rates frow the reactor coolant system have beenbased on the predicted -and exyerfaentally observed behavior Of CraCks inyipes. The nomally exyected background leakage due to equipment design andthe detection capability of the )nstruoentatfon for deterefnfng systei leakage~as also considere4. The evidence obtained free experfaentS SuggeStS that forleakage see@mat greater Chan that spec)fied for UNIOKMTIFIKO LEAKAGK theprobability fs asall that the faperfectfon or- crack associated ~1th such leakagewould ~ ra 141 . Heaver, fn all cases, ff the leakage rates exCee4 theva ues spec)f e4 or the leakage fs located and kncwn to be PRESSURE NQIOARYLEAKAGK, the reactor r)11 be shutdae to aller further investigation andcorrective action.

The Surveillance lequfreoents for NCS pressure isolation valves provide~ 4ded assurance of valve fntegrfty thereby reducing the probab)1)ty of grossvalve failure an4 cansaqwnt )ntarsystee LOCA.

The uater cheafstry l)Nts of the reactor coolant systole are establ)shedto prevent daeege to the reactor eaterfals fn contact Hth the coolant. Chloride11 ~ fts are syec)f1ed ta prevent stress corrosion cracking of the stainless steel.The effect of chlor)de fs net as great ~n the oxygen concentration )n thecoolant is low, thus the 0.2 ppa i)aft on chlorides fs perwftted during Wheal

OPBATIN. Ourfng shutdem and refuel)ng oyeratfons, the teaperature necessaryfo'r stress corros)on 'to occur fs not present so ~ Oo S Qpo cohceh'trat1on ofchlor)des fs not cons)4ere4 hateful during these per)ods

SUSglBQNA WIT 1 a 3/442 Ieen4sent lfo. 5i

AP PL ICABILITY

SURV'EILLANCE RE UIREMEHTS

4.0.1 Surveillance Requirements shall be met during the OP'ERATIOHAL CONOIT?ONSor other conditions specif ed for individual Limiting Conditians for Operationunless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be per formed within the soeci"fiedsurveillance interval with a maximum allowable extension not to exceed 25percent of the specified surveillance interval.

4.0.3 Faiiure to perform a Sur evil'I acne acquirement vithin -na aiiovedsurveilianca !nterval, defined hv 5 oeicrication a.0.2, shall co nstir ut a

noncompliance with the OPERASILIT'f requirements for a Limiting Conditionfor Operation. The time limits of the ACTION requirements are applicableat the time it is identified that a Surveillance Requirement nas not eenerformed.:he ACTION reauirements wa oe dela ed for uo 'a 24 nau toermit the " mOletian Of the SurVeillanCe wnen the allOWable Outa e. ime

limits of the ACTION requirements are less than 24 hours. urvei1 lanceRequirements da not have to be pe~formed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL COHOITION or other specified applicablecondition shall not be made unless the Surveillance Requirement(s) associatedwith the Limiting Condition for Operation have been performed within theapplicable surveillance interval or as atherwise specified. This orovisionshall not revent oassa e throu h or to OPERATIONAL CONOITIOHS as r equi< ed tocomp 1 wi th ACTION re ui rements.

4. 0. 5 Surveillance Requirements for inservice inspection .and testing of ASMECode Class 1, 2, & 3 components shall be applicable as follows:

a.

b.

Inservice inspection oi'SME Code Class 1, 2, and 3 comoonents andinservice testing of ASME Cade Class 1, 2, and 3 pumps and valvesshall be perfarmed in accordance with Section XI of the ASME Boilerand Pressure Vessel Code and applicable Addenda as required by10 CFR 50, Section 50. 55a(g), except where speci fic written reliefhas been granted by the Commission pursuant to 10 CFR 50,Section 50.55a(g)(6)(i).

Surveillance intervals specified in Section XI of the ASME Boilerand Pressure Vessel Code and applicable Addenda for the inserviceinspection and testing activities required by the ASME Boiler andPressure Vessel Code and applicable Addenda shall be applicable asfollows fn these Technical Specifications:

" ot app 'cable to month surve'ances r ired to b erformed p 'or tot start fol lowing e end of t Unit 2 Th'efuel > and Inspec

'

Out e.

SUSQUEHANNA " UNIT 2 3t4 0-2 Amendment Na., 65

APPLICABILITY

SURVEILLANCE RE UIREMENTS Continued

ASME Boiler and Pressure VesselCode and applicable Addendaterminology for inserviceinspection and testin activities

WeeklyMonthly

quarterly or every 3 monthsSemiannually or every 6 months

Every 9 monthsYearly or annually

Required frequenciesfor performing inserviceinspection and testingactivitiesAt least once per 7 daysAt least once per 3I daysAt least once per 92 daysAt least once per 184 daysAt least once per 276 daysAt least once per 366 days

C. The provisions of Specification 4.0.2 are applicable to the aboverequired .frequencies for performing inservice inspection and testingactivities.

ADD

d. Performance of the above inservice inspection and testing activitiesshall be in addition to other specified Surveillance Requirements.

Nothing in the ASME Boiler and Pressure Vessel Code shall beconstrued to superse'de the requirements of any Technicalpec~ieat4a~

The Inservice Inspection Program forpiping identi6ed in NRCGeneric Letter 88-01 shall be performed in accordance with the NRCStaQ'position on Schedule, Methods and Personnel, and sampleexpansions included in the Generic Letter.




LEAKAGE DETECTION SYSTEMS


3.4.3. 1 At least the following reactor coolant system leakage detectionsystems shall be OPERABLE:

a. Two drywell floor drain sump level channels, and

b. One primary containment atmosphere gaseous radioactivity monitoringsystem channel and one containment atmosphere particulateradioactivity monitoring system channel aligned to the drywell.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a. With one or both channels of the drywell floor drain sump levelmonitoring system inoperable be in at least HOT SHUTDOWN within the

d in COLD SH TDOWN within the following 24 hours.CARAgCd Ml4 CCuguur FCA ~»m

o annels of the gaseous radioactivity monitoring systeminoperable or with both channels of the particulate radioactivityonitoring system inoperable, operation may continue for up to 30~~~ >~~8 ~ ays provided grab samples of the containment atmosphere are

@m 1s Mw<~q~ tained and analyzed at least once per 24 hours. If at least onehannel of the affected monitoring system cannot be returned toPERABLE status and aligned to the drywell within 30 days, 'or the~~~ KM~S~~ rab samples are not obtained and analyzed as required, be in at

Lt=czz~cc ~1~ east HOT SHUTDOWN within the next 12 hours and in COLO SHUTDOWNithin the following 24 hours ~


4.4.3.1 The reactor coolant system leakage detection systems shall bedemonstrated OPERABLE by:

Primary containment atmosphere particulate and gaseous monitoringsystems-performance of a CHAANEL CHECK at least once per 12 hours, aCHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNELCALIBRATION at least once per 18 months.

b. Orywell floor drain sump level monitoring system-performance of aCHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNELCALIBRATION at least once per 18 months.

SUSQUEHANNA - UNIT 2 3/4 4-6 Amendment No; 53


OPERATIONAL LEAKAGE


3.4.3.2ao

Reactor coolant system leakage shall be limited to:No PRESSURE BOUNDARY LEAKAGE.

b.

C.

d.

e.

APPLICABIL S1,2, and3.

ACTION:

5 gpm UNIDENTIFIED LEAKAGE.

25 gpm total leakage averaged over any 24-hour period.1 gpm leakage at a.reactor coolant system pressure of 1000 k 10 psigfrom any reactor coolant system pressure isolation valve specifiedin Table 3.4.3.2-1.~pm-iecmase-4n-UM IEO LEAKAGE within any -hour peri os4 WEwnaure CDJDNDU 3..

a.

b.

C.

d.

e.

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within12 hours and in COLO SHUTDOWN within the next 24 hours.

With any reactor coolant system leakage greater than tge limits in b.and/or. c., above, reduce the leakage rate to within the limits within4 hours or be in at least HOT SHUTDOWN within the next 12 hours andin COLD SHUTDOWN within the following 24 hours.

With any reactor coolant system pressure isolation valve leakagegreater than the above limit, isolate the high pressure portion of theaffected system from the low pressure portion within 4 hours by useof at least one closed manual or deactivated automatic valve, or bein at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN

within the following 24 hours.

With one or more of the high/low pressure interface valve leakagepressure monitors shown in Table 3.4.3.2-1 inoperable, restore theinoperable monitor(s) to OPERABLE status within 7 days or verify thepressure to be less than the alarm pressure at least once per 12 hours;restore the inoperable monitor(s) to OPERABLE status within 30 days orbe in,at least HOT SHUTDOWN within the next 12 hours and in COLD

SHUTOOWN within the fo11owing 24 Pops.,u g„eWith any reactor coolant system ENTIFIEO L increasegreater than 2 gpa within any $-hour period, identify the sourceof leakage increase as not service sensitive Type 304 or 316austenitic stainless steel within hours or be in at leastHOT SHUTDOWN within the next 12 hours and in COLO SHUTDOWN withinthe following 24 hours.

SUSQUEHANNA " UNIT 2 3/4 4-7



I

4.4.3.2. 1 The reactor coolant system leakage shall be demonstrated to bewithin each of the above limits by;

a. Monitoring the primary containment atmospheric particulate andgaseous radioactivity at least once per 4 hours, and

*

b. Monitoring the drywell floor drain sump level at least once perurs.

c. Oetermining the total IDENTIFIEO LEAKAGE at least once per 24 hours.

4.4.3.2.2 Each reactor coolant system pressure isolation valve specified inTable 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing pursuant toSpecification 4.0.5 and verifying the leakage of each valve to be withi thespecified limit:

a. At least once per 18 months, and

b. Prior to returning the valve to service following maintenance, repairor replacement work on the valve which could affect its leakage rate.

The provisions of Specification 4.0.4 are not applicable for"entry intoOPERATIONAL CONOITION 3.

4. 4. 3. 2. 3 The high/low pressure interface valve leakage pressure monitors shallbe demonstrated OPERABLE with the alarm setpoints per Table 3.4.3.2-1 byperformance of a:

a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and

b. CHANNEL CALIBRATION at least once per 18 months.


REACTOR COOLANT SY

BASES

9

4i

4Pj

gbn 0

g2

r-,$

3)g g

Recirculation pump speed mismatch limits are in compliance with the ECCS LOCAanalysis design criteria for two loop operation. The limits will ensu~e anadequate core'flow coastdown from either reCirCulation loop following a LOCA.In the CaSe where the miSmatCh limitS CannOt be maintained during the lOOp

'peration,continued operation is permitted in the single loop mode.

In order to prevent undue stress on the vessel nozzles and bottom head region,the recirculation loop temper atures shall be within 50oF of each other priorto startup of an idle loop. The loop temperature must also be within 504F ofthe reactor pressure vessel coolant temperature to prevent thermal shock to therecirculation pump and recirculation nozzles. Since the coolant in the bottomof the vessel is at a lo~er temperature than the coolant in the upper regionsof the core, undue stress on the vessel would result if the temperature differ-ence was greater than 1454F.

lsty of gross

Amendment No.60

Auv 2d tSN

3/4.4.2 SAFETY/RELIEF VALVES% ~

The safety valve function of the safetv/relief valves operate to prevent the;reactor coolant system from being pressurized above the Safety Limit of 1325 psigin accordance with the ASME Code. A total of 10 OPERABLE safety/relief valvejis required to limit reactor pressure to within ASME III allowable values for-the worst case upset transient.

Oemonstration of the safety/relief valve lift settings will occur only duringShutdown and will be performed in accordance with the provisions of Specifica-tion 4.0.5.


3/4.4.3. 1 LEAKAGE OETFCTION SYSTEMS

The RCS leakage detection systems required by this specification areprovided to monitor and detect leakage from the reactor coolant pressureboundary.

3/4. 4. 3. 2 OPERATIONAL LEAKAGE

The allo~able leakage rates from the reactor coolant system have beenbased on the predicted and experimentally observed behavior of cracks inpipes. The normally expected background leakage due to equipment design andthe detection capability of the instrumentation for determining system leakagewas also considered. The evidence obtained from experiments suggests that forleakage some~hat greater than that sPecified for UNIOENTIFIEO LEAKAGE theprobability is small that the imperfection or crack associated with such leakagewould grow rapidly.'owever, in all cases, if the leakage rates exceed theva ues spec ie or the leakage is located and known to be PRESSURE 80UNOARY

LEAKAGE, the reactor will be shutdown to allo~ further investigation andcorrective action.

The Surveillance Requirements for RCS pressure isolation valves provideadded assurance of valve integrity thereby reducing the probabivalve failure and consequent intersystem LOCA.

SUSQUEHANNA - UNIT 2 B 3/4 4-2

,h

F'

proposed ts 3/4.4.3, 'rcs leakage,leakage detection sys.' · re'actor coolant system...

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